Solidification of high level wastes. Part IV. Phosphate melts for fixation of radioactive residues from Purex type wastes: three to fifty percent fission product oxides

Technical Report · Thu Jul 01 00:00:00 EDT 1965

OSTI ID:5491869

Barton, G B

The possible composition range for the high-level radioactive wastes generated from various power reactor fuels processed through a Purex-type process is very broad. A partial survey of this wide range was conducted in an effort to establish the composition limits that bound the operable range of the phosphate melt system. Two screening criteria were used: (a) drip temperature, an empirical measure of flow temperature at which a container could be filled, and (b) solubility. Measurements indicated the occurrence of two (or possibly more) optimum phosphate additions near M/sub 2/O/P/sub 2/O/sub 5/ ratios of 2.1 and 1.0. It was found that fission products equivalent to at least 50% of the weight of oxides in the plant waste can be successfully incorporated in a phosphate melt that can be transferred as a fluid into containers at less than 900/sup 0/C.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (USA)
• OSTI ID: 5491869
• Report Number(s): BNWL-80
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
RADIOACTIVE WASTE PROCESSING
FEASIBILITY STUDIES
HIGH-LEVEL RADIOACTIVE WASTES
SOLIDIFICATION
PHOSPHATES
PUREX PROCESS
MANAGEMENT
MATERIALS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PHOSPHORUS COMPOUNDS
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REPROCESSING
SEPARATION PROCESSES
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
052001* - Nuclear Fuels- Waste Processing